ML19344E964
| ML19344E964 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/06/1980 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-17, NUDOCS 8009120179 | |
| Download: ML19344E964 (2) | |
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Jersey Central Power & Light Company
- l k Madison Avenue at Punch Bowl Road Momstown, New Jusey 07960 (201)455-8200 August 6, 1980 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 I E Bulletin No. 80-17
References:
(a)
Ivan R. Finfrock, Jr. letter to Boyce H. Grier, dated July 11, 1980.
(b) Donald A. Ross letter to Boyce H. Grier, dated July 16, 1980.
(c)
Ivan R. Finfrock, Jr. letter to Boyce H. Grier, dated July 24, 1980.
The subject bulletin required certain actions by BWR licensees as a result of 76 control rods failing to insert at TVA's Browns Ferry Unit No.
3.
Specifically, I E Bulletin 80-17 described eight (8) action items. Via references (a) thru (c) required responses to items 1.,
2.,
4.,
5., 6.(a) and 6.(c) were forwarded to your office. The purpose of this letter is to provide responses for the remaining items (3., 6.(b), 7 and 8).
It should be noted that a re-statement of items is not included in this response.
However, the specific item number referenced corresponds to those given in the original bulletin.
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ltem 3 Ultrasonic testing of the SDV and associated piping was performed subsequent to scram testing.
No significant amount of water was detected.
Also, all applicable procedures have been revised to insure verification that no significant amount of water is present in the SDV and associated i
piping subsequent to any scram.
.8 0 0 912 0 17f Jeav C@ nerd Power & Let Company is a Member of the General n byc Util!ies System u
.y Boyce H. Grier, Director August 6, 1960 Item 6.(b)
In order to mitigate the consequences of an ATWS event at Oyster Creek Nuclear Generating Station procedures require the initiation of all available suppression pool cooling whenever normal operating limits for the system are exceeded.
Item i' Oyster Creek Nut h'ar Generating Station systems design does incorpcrate ATWS related RpT.
Therefore, no further action is considered necessary.
The information recorded above, in conjunction with responses forwarded via references (a) thru (c) constitute completion of all requirements invoked by the subject bulletin as described in ITEM 8.
)k Ivan R. Finfr k,
Vice Presiden Ge ration IRF:JMD:dh cc: NRC Office of Inspection and Enformement Division of Reactor Operations Inspection U. S. Nuclear Regulatory Commission Washington, D. C.
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